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Aluminum Cladding Long Uranium Plates by Solid-State Bonding

Description: From introduction: This report covers an investigation of solid-state bonding as a technique for aluminum cladding uranium plates of 3 by 0.180-in. cross section in lengths up to 14 ft.
Date: March 29, 1955
Creator: Saller, Henry A.; Dickerson, R. F. & Carlson, R. J.
Partner: UNT Libraries Government Documents Department

The Ammonium Carbonate Pressure Leaching of Uranium Ores Proposed as Feed to the Pilot Plant at Grand Junction, Colorado : Progress Report

Description: From introduction: This is Progress report BMI-282, the first of a series covering the operation of the pressure-leaching towers for the extraction of uranium by an ammonium carbonate leach...This report discusses the data obtained from tests run to show the effects of such variables as the amount of air and carbon dioxide passed through the pulp, temperature, pressure, and concentration of ammonium carbonate and ammonium bicarbonate in the leach solution on the extraction of uranium.
Date: June 15, 1955
Creator: Wheeler, C. M.; Langston, B. G. & Stephens, F. M.
Partner: UNT Libraries Government Documents Department

Alloys of Uranium with Zirconium, Chromium, Columbium, Vanadium, and Molybdenum

Description: Abstract: Information on five uranium binary alloy systems has been surveyed. These systems are the alloys of uranium with zirconium, chromium, columbium, vanadium, and molybdenum. The equilibrium diagrams are discussed, and where available, data have been included on diffusion studies, cladding experiments, and mechanical properties.
Date: June 19, 1952
Creator: Saller, Henry A. & Rough, Frank A.
Partner: UNT Libraries Government Documents Department

An evaluation of data on zirconium-uranium alloys

Description: Report describing the literature relative to zirconium-uranium alloys. The available data related to zirconium-uranium alloys is analyzed in an attempt to understand the behavior and nature of the alloy. Other aspects of zirconium-uranium alloys are discussed in the report.
Date: 1955
Creator: Rough, Frank A.
Partner: UNT Libraries Government Documents Department

The technology of thorium

Description: A report describing the technological uses of thorium. The report details interest in thorium as a potential source of the fissionable isotope U233 as well as possessing other applications. Most of the information in this report was obtained from project literature and from unpublished data available to the authors.
Date: 1951
Creator: Marsh, L. L. & Keeler, J. R.
Partner: UNT Libraries Government Documents Department

Temperature distributions in a reactor fuel plate

Description: Report detailing local heat-transfer coefficients as they relate to temperature distribution in reactor fuel plates.
Date: 1953
Creator: Chastain, Joel W.; Long, J. K.; Redmond, R. F.; Grimble, R. E. & Dayton, R. W.
Partner: UNT Libraries Government Documents Department

Aqueous Corrosion of Uranium Fuel-Element Cores Containing 0 to 20 w/o Zirconium

Description: Abstract: A description is given of the design and operation of a windowed autoclave system employed in the study of corrosion by pressurized hot water. The device has been used to obtain time-lapse motion pictures of the swelling and rupture of deliberately defected zirconium-clad uranium specimens. A method is described by which corrosion rates were calculated from pressure and temperature measurements. A typical set of pictures taken during a test is presented, and corrosion rates are reported for uranium-0, 5, 10, 15, and 20 w/o zirconium alloys subjected subjected to 600 F water.
Date: January 7, 1957
Creator: Grieser, Daniel R. & Simons, Eugene M.
Partner: UNT Libraries Government Documents Department

Apparatus for visual study of corrosion by hot water

Description: Report describing an apparatus for visual study of corrosion of uranium by hot water. A windowed autoclave was designed and constructed to permit visual study of the reaction under conditions simulating a cladding failure in service.
Date: 1955
Creator: Grieser, Daniel R. & Simons, Eugene M.
Partner: UNT Libraries Government Documents Department

Annealing of crystal distortion in irradiated graphite

Description: From introduction: "As part of the program for improvement of graphite, the structural characteristics of graphite have been studied to determine the relation between physical and structural changes during irradiation."
Date: 1955
Creator: Austin, Alfred E. & Harrison, Ralph J.
Partner: UNT Libraries Government Documents Department

The Application of Ceramics to Hanford Fuel Elements

Description: From introduction: This work is a survey of possible uses of ceramic materials in Hanford-type fuel elements.
Date: September 4, 1953
Creator: King, B. W.; Tripp, H. P. & Duckworth, W. H.
Partner: UNT Libraries Government Documents Department

An Application of the Concepts of Particle Packing to the Consolication of Silicon Carbide Powders

Description: From introduction: Silicon carbide is being considered as a basis material for nonmetallic fuel elements because of its high thermal conductivity, low nuclear cross section, high resistance to thermal rupture, and high degree of stability at high temperature in air. A requirement of the fuel elements is that they be thin and have as low porosity as possible. One shape of element under consideration is 0.050 to 0.070 inch thick by a few inches in width and breadth.
Date: August 15, 1952
Creator: Harman, Cameron G.; Shinn, J. & Wagner, H. E.
Partner: UNT Libraries Government Documents Department

Beryllia and Beryllia-Beryllium Bodies for Moderating Cores in Fuel Elements

Description: From introduction: This report presents the results of the two phases of the work: study of the compatibility of beryllia bodies with a coating material, molybdenum; and studies of beryllia-beryllium body fabrication.
Date: July 31, 1952
Creator: Long, R. E.; Duckworth, W. H.; Saller, Henry A.; Stacy, J. T.; Miller, R. A. & Schofield, H. Z.
Partner: UNT Libraries Government Documents Department

Beta-Counting Methods Applied to the Determination of Uranium in Low-Grade Ores

Description: The following report covers investigations on the application of the beta counter as an analytical tool for use in experiments on the extraction and concentration of uranium from low-grade (.005-.02 % uranium) shale and phosphate rock ores.
Date: July 1947
Creator: Doig, J. R.; Igelsrud, Iver; Nelson, H. R. & Schwartz, C. M.
Partner: UNT Libraries Government Documents Department

Centrifugal Casting of Aluminum-Uranium Alloys

Description: "Centrifugal-casting techniques were investigated as a method of producing hollow cylindrical extrusion billets of aluminum-35 w/o uranium. Among the variables evaluated were melt temperature, mold and pouring-spout configurations, mold speed, and method of pouring. With the equipment employed it was found that the best castings were produced stilizing a pouring temperature of 2400 F, a heavy-walled steel cylinder rotating between 700 to 900 rpm for the mold and bottom-pouring technique employing a retractable pouring spout. Sound, nonporous billets 26 in. long and 5 in. in diameter were produced with a yield after machining of over 75 per cent of the original charge. The major losses occurred in the pouring spout-and-cup assembly. This loss is relatively unaffected by the casting length; and, therefore, coatings of greater length than 26 in. should results in even greater recoveries.
Date: July 20, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department

Composition of vapors from boiling nitric acid solutions

Description: From abstract: "The composition of vapors from aqueous nitric acid solutions boiling at 200 mm mercury total pressure is established for solutions containing between - and 67.5 w/o nitric acid. The volatility characteristics of low concentrations of chloride in the same concentration range of nitric acid have been measured in solutions boiling at 200 mm mercury. The effects of chloride concentration and pressure of boiling are evaluated. A spectrophotometric method of the determination of chloride in nitric acid solutions is described."
Date: February 9, 1955
Creator: Crooks, R. C.; Wilson, R. Q.; Bearse, A. E. & Filbert, Robert B.
Partner: UNT Libraries Government Documents Department

Corrosion of thorium and uranium during long-term storage

Description: From introduction: "The over-all objective of the present study was to determine the nature and extent of the present study was to determine the nature and extent of the corrosion of these materials under a variety of such storage conditions and to determine the ability of several potential protective coatings to retard this corrosion."
Date: April 10, 1962
Creator: Stephan, Elmer F.; Miller, P. D. & Fink, Frederick W.
Partner: UNT Libraries Government Documents Department

Ceramic Investigations of UO₂

Description: This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date: June 16, 1955
Creator: Allison, Adrian G. & Duckworth, Winston Howard, 1918-
Partner: UNT Libraries Government Documents Department

Characterization of Inclusion in Dingot Uranium

Description: Abstract: The nonmetallic inclusions in both as-reduced and fabricated dingot uranium have been studied for comparison with those in ingot uranium. Special attention was paid to the hydride for the purpose of determining the amount and distribution in the various types of uranium. The types and distribution of other inclusions were also studied. It was found that the dingot uranium was of a higher quality than ingot uranium and was comparable to as-reduced derby uranium on the basis of over-all inclusion count. The hydrogen content in dingot uranium, however, was found to be appreciably higher than in either ingot or derby uranium.
Date: January 11, 1957
Creator: Cheney, Donald M. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department

Hazards Summary Report for the Battelle Research Reactor

Description: From summary: "This report was prepared for the Advisory Committee on Reactor Safeguards for their review and consideration of the potential hazards concerning the Battelle Memorial Institute Research Reactor."
Date: April 4, 1955
Creator: Chastain, J. W.
Partner: UNT Libraries Government Documents Department

Numerical Results for EGCR Moderator-Element Stress Problems

Description: From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."
Date: July 3, 1961
Creator: Hulbert, Lewis E.
Partner: UNT Libraries Government Documents Department

The Solubility of Oxygen in Uranyl Sulphate Solutions at Elevated Temperatures

Description: Abstract: "The solubility of oxygen in uranyl sulphate solutions and in water at 212, 275, and 325 F, and at oxygen partial pressures up to 1500 psia was investigated. The results are presented in tabular and graphic form. The solubility is proportional to the partial pressure of oxygen. The ratio of solubility in the uranyl sulphate solution to solubility in water at the same temperature and pressure is a function of the concentration of the salt in solution."
Date: June 10, 1953
Creator: Pray, H. A. & Stephan, Elmer F.
Partner: UNT Libraries Government Documents Department

Uranium Migration in UO₂-Bearing Ceramics

Description: This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.
Date: September 4, 1953
Creator: Quirk, J. F.; Smalley, A. K.; Duckworth, W. H. & Ferrell, Edward Francis.
Partner: UNT Libraries Government Documents Department